ML25233A262
| ML25233A262 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, Ginna  |
| Issue date: | 09/02/2025 |
| From: | Scott Wall Plant Licensing Branch III |
| To: | Rhoades D Constellation Energy Generation |
| Wall, SP | |
| References | |
| EPID L-2025-LLA-0043 TSTF-309 | |
| Download: ML25233A262 (1) | |
Text
September 2, 2025 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; AND R.E. GINNA NUCLEAR POWER PLANT - ISSUANCE OF AMENDMENTS TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-309 (EPID L-2025-LLA-0043)
Dear Mr. Rhoades:
The U.S. Nuclear Regulatory Commission (NRC or Commission) has issued the enclosed amendments (listed below) in response to the Constellation Energy Generation, LLC (CEG) application dated February 27, 2025:
- 1.
Amendment No. 243 to Renewed Facility Operating License No. NPF-72 and Amendment No. 243 to Renewed Facility Operating License No. NPF-77 for Braidwood Station, Units 1 and 2, respectively;
- 2.
Amendment No. 241 to Renewed Facility Operating License No. NPF-37 and Amendment No. 241 to Renewed Facility Operating License No. NPF-66 for Byron Station, Unit Nos. 1 and 2, respectively; and
- 3.
Amendment No. 159 to Renewed Facility Operating License No. DPR-18 for R.E. Ginna Nuclear Power Plant.
The amendments revise the technical specifications (TSs) for each facility in accordance with Technical Specifications Task Force (TSTF) Traveler 309, Revision 2, Revise Pressurizer PORV [Pressurizer Power Operated Relief Valves] Actions to not require cycling of block valve when closed for isolation, Specifically, TSTF-309 revises the TS 3.4.11 to add notes stating that the Required Actions do not apply if the PORV block valve was declared inoperable solely as a result of complying with other Required Actions in TS 3.4.11.
A copy of the NRC staffs Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Scott P. Wall, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: STN 50-456, STN 50-457, STN 50-454, STN 50-455, and 50-244
Enclosures:
- 1. Amendment No. 243 to NPF-72
- 2. Amendment No. 243 to NPF-77
- 3. Amendment No. 241 to NPF-37
- 4. Amendment No. 241 to NPF-66
- 5. Amendment No. 159 to DPR-18
- 6. Safety Evaluation
- 7. Notices and Environmental Findings cc: Listserv
CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 243 Renewed License No. NPF-72
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated February 27, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the renewed license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-72 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 243 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: September 2, 2025 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2025.09.02 13:31:34 -04'00' CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 243 Renewed License No. NPF-77 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated February 27, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the renewed license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-77 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 243 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: September 2, 2025 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2025.09.02 13:32:09 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 243 AND 243 RENEWED FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating Licenses REMOVE INSERT License NPF-72 License NPF-72 Page 3 Page 3 License NPF-77 License NPF-77 Page 3 Page 3 Technical Specifications REMOVE INSERT 3.4.11 - 2 3.4.11 - 2 3.4.11 - 3 3.4.11 - 3 3.4.11 - 4 (2)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 243 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed License No. NPF-72 Amendment No. 243 (2)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
The renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 243 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed License No. NPF-77 Amendment No. 243
ACTIONS (continued)
CONDITION C. One block valve C.l inoperable.
AND C.2 D. Required Action and 0.1 associated Completion Time of Condition A, AND B, or C not met.
0.2 E. Two PORVs inoperable E.1 and not capable of being manually cycled. AND E.2 BRAIDWOOD - UNITS 1 & 2 REQUIRED ACTION
NOTE---------
Required Actions C.1 and C.2 do not apply when block valve is inoperable solely as a result of complying with Required Action B.2.
Place associated PORV in manual control.
Restore block valve to OPERABLE status.
Be in MODE 3.
Be in MODE 4.
Be in MODE 3.
Be in MODE 4.
3.4.11 - 2 Pressurizer PORVs 3.4.11 COMPLETION TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 72 hours OR In accordance with the Risk Informed Completion Time Program 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours (continued)
Amendment 243
ACTIONS (continued)
CONDITION F. Two block valves F.1 inoperable.
G. Required Action and associated Completion G.l Time of Condition F AND not met.
G.2 BRAIDWOOD -UNITS 1 & 2 REQU I RED ACTION
NOTE---------
Required Action F.1 does not apply when block valve is inoperable solely as a result of complying with Required Action B.2.
Restore one block valve to OPERABLE status.
Be in MODE 3.
Be in MODE 4.
3.4.11-3 Pressurizer PORVs 3.4.11 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 6 hours 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Amendment 243
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.11.1
NOTE-------------------
Not required to be met with block valve closed in accordance with the Required Action of Condition B or E.
Perform a complete cycle of each block valve.
NOTE-------------------
Only required to be performed in MODES 1 and 2.
Perform a complete cycle of each PORV.
SR 3.4.11.3 Perform a complete cycle of each solenoid air control valve and check valve on the air accumulators in PORV control systems.
BRAIDWOOD -UNITS 1 & 2 3.4.11-4 Pressurizer PORVs 3.4.11 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment 243 CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 241 Renewed License No. NPF-37 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated February 27, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the renewed license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-37 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 241 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: September 2, 2025 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2025.09.02 13:32:39 -04'00' CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. STN 50-455 BYRON STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 241 Renewed License No. NPF-66 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated February 27, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-66 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 241, and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: September 2, 2025 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2025.09.02 13:33:00 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 241 AND 241 RENEWED FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating Licenses REMOVE INSERT License NPF-37 License NPF-37 Page 3 Page 3 License NPF-66 License NPF-66 Page 3 Page 3 Technical Specifications REMOVE INSERT 3.4.11 - 2 3.4.11 - 2 3.4.11 - 3 3.4.11 - 3 3.4.11 - 4 (2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
The renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 241 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Deleted.
(4)
Deleted.
Renewed License No. NPF-37 Amendment No. 241 (2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
The renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 241, and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Deleted.
Renewed License No. NPF-66 Amendment No. 241
ACTIONS (continued)
CONDITION C. One block valve C.1 inoperable.
AND C.2 D. Required Action and 0.1 associated Completion Time of Condition A, AND B, or C not met.
0.2 E. Two PORVs inoperable E.1 and not capable of being manually cycled. AND E.2 BYRON - UNITS 1 & 2 REQUIRED ACTION
NOTE---------
Required Actions C.1 and C.2 do not apply when block valve is inoperable solely as a result of complying with Required Action B.2.
Place associated PORV in manual control.
Restore block valve to OPERABLE status.
Be in MODE 3.
Be in MODE 4.
Be in MODE 3.
Be in MODE 4.
3.4.11 - 2 Pressurizer PORVs 3.4.11 COMPLETION TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 72 hours OR In accordance with the Risk Informed Completion Time Program 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours (continued)
Amendment 241
ACTIONS (continued)
CONDITION F. Two block valves F.1 inoperable.
G.
Required Action and associated Completion G.1 Time of Condition F AND not met.
G.2 BYRON - UNITS 1 & 2 REQUIRED ACTION
NOTE---------
Required Action F.1 does not apply when block valve is inoperable solely as a result of complying with Required Action B.2.
Restore one block valve to OPERABLE status.
Be in MODE 3.
Be in MODE 4.
3.4.11 - 3 Pressurizer PORVs 3.4.11 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 6 hours 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Amendment 241
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.11.1
NOTE-------------------
Not required to be met with block valve closed in accordance with the Required Action of Condition B or E.
Perform a complete cycle of each block valve.
NOTE-------------------
Only required to be performed in MODES 1 and 2.
Perform a complete cycle of each PORV.
SR 3.4.11.3 Perform a complete cycle of each solenoid air control valve and check valve on the air accumulators in PORV control systems.
BYRON - UNITS 1 & 2 3.4.11 - 4 Pressurizer PORVs 3.4.11 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment 241 R. E. GINNA NUCLEAR POWER PLANT, LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-244 R. E. GINNA NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 159 Renewed License No. DPR-18 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated February 27, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-18 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 159, are hereby incorporated in the renewed license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: September 2, 2025 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2025.09.02 13:33:30 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 159 RENEWED FACILITY OPERATING LICENSE NO. DPR-18 R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License DPR-18 License DPR-18 Page 4 Page 4 TSs TSs 3.4.11 - 2 3.4.11 - 2 3.4.11 - 3 3.4.11 - 3 R. E. Ginna Nuclear Power Plant Amendment No. 159 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 159, are hereby incorporated in the renewed license.
Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.
(3)
Fire Protection Constellation Energy Generation, LLC shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensees amendment request dated March 28, 2013, supplemented by letters dated December 17, 2013; January 29, 2014; February 28, 2014; September 5, 2014; September 24, 2014; December 4, 2014; March 18, 2015; June 11, 2015; August 7, 2015; and as approved in the safety evaluation report dated November 23, 2015. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.
(a)
Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant. Acceptable methods to assess the risk of the change may include methods that have been used in the peer-reviewed fire PRA model, methods that have been approved by NRC through a plant-specific license amendment or NRC approval of generic methods specifically for use in NFPA 805 risk assessments, or methods that have been demonstrated to bound the risk impact.
1.
Prior NRC review and approval is not required for changes that clearly result in a decrease in risk. The proposed change must also be consistent with the defense in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.
Pressurizer PORVs 3.4.11 CONDITION REQUIRED ACTION COMPLETION TIME AND B.3.2.2 Restore PORV to OPERABLE status 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR
NOTE------
Not applicable if there is a loss of function.
In accordance with the Risk Informed Completion Time Program C.
One block valve inoperable.
NOTE---------------
Required Actions C.1 and C.2 do not apply when block valve in inoperable solely as a result of complying with Required Action B.2 or F.3.
C.1 Place associated PORV in manual control.
AND C.2.1 Restore block valve to OPERABLE status.
OR C.2.2.1 Verify Opposite Train PORV and PORV Block Valve are OPERABLE AND C.2.2.2 Restore PORV Block Valve to OPERABLE status 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 days 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 days OR (continued)
R.E. Ginna Nuclear Power Plant 3.4.11-2 Amendment 159
Pressurizer PORVs 3.4.11 CONDITION REQUIRED ACTION COMPLETION TIME
NOTE------
Not applicable if there is a loss of function.
In accordance with the Risk Informed Completion Time Program D.
Both block valves inoperable.
NOTE---------------
Required Actions D.1 and D.2 do not apply when block valve is inoperable solely as a result of complying with Required Action B.2 or F.3.
D.1 Place associated PORVs in manual control.
AND D.2 Restore at least one block valve to OPERABLE status.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 72 hours E.
Required Action and associated Completion Time of Condition A, B, C, or D not met.
E.1 Be in MODE 3.
AND E.2 Be in MODE 4.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours F.
Two PORVs inoperable.
F.1 Initiate action to restore one PORV to OPERABLE status.
AND F.2 Close associated block valves.
AND F.3 Remove power from associated block valves.
AND F.4 Be in MODE 3 with Tavg
< 500 F.
Immediately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> R.E. Ginna Nuclear Power Plant 3.4.11-3 Amendment 159 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 243 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-72 AMENDMENT NO. 243 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-77 AMENDMENT NO. 241 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-37 AMENDMENT NO. 241 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-66 AMENDMENT NO. 159 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-18 CONSTELLATION ENERGY GENERATION, LLC BRAIDWOOD STATION, UNITS 1 AND 2 BYRON STATION, UNIT NOS. 1 AND 2 R.E. GINNA NUCLEAR POWER PLANT DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, STN 50-455, AND 50-244 Application (i.e., initial and supplements)
Safety Evaluation Date
February 27, 2025, ML25058A246 September 2, 2025 Principal Contributor to Safety Evaluation
Steve Smith
1.0 PROPOSED CHANGE
S Constellation Energy Generation, LLC (CEG, the licensee) requested changes to the technical specifications (TSs) for Braidwood Station, Units 1 and 2 (Braidwood), Byron Station, Unit Nos. 1 and 2 (Byron), and R.E. Ginna Nuclear Power Plant (Ginna) by license amendment request (LAR, application) to the U.S. Nuclear Regulatory Commission (NRC, the Commission).
The proposed changes would revise the TSs for each facility based on Technical Specifications Task Force (TSTF) Traveler 309, Revision 2, Revise Pressurizer PORV [Power Operated Relief Valve] Actions to not require cycling of block valve when closed for isolation, (TSTF-309)
(Agencywide Documents Access and Management System (ADAMS) Accession No. ML040620179)). Specifically, TSTF-309 revises the standard TS (STS) by modifying TS 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), to add notes stating that the Required Actions do not apply if the PORV block valve was declared inoperable solely as a result of complying with other Required Actions in TS 3.4.11.
The changes in TSTF-309, Revision 2, were approved by the NRC in \
letter dated July 26, 1999 (ML19067A141), and incorporated into NUREG-1431, Standard Technical Specifications Westinghouse Plants Volume 1, Specifications, and Volume 2, Bases, Revision 2, June 2001 (ML031270565 and ML031270580, respectively).
1.1 System Description Pressurized water reactor (PWR) pressurizer PORVs are air operated valves that open at a specific pressure when the pressurizer pressure increases and close when the pressurizer pressure decreases. PORVs may also be manually operated from the control room.
Normally open motor-operated block valves are located between the pressurizer and the PORVs and are used to isolate the PORVs in case of excessive leakage. Block valves are operated manually from the control room. Excessive leakage or a stuck open PORV is, in effect, a small break Loss of Coolant Accident (LOCA). Closing the block valve stops the leakage and any associated reactor coolant system (RCS) depressurization and coolant inventory loss.
PORVs and their associated block valves may be used by plant operators to depressurize the RCS to recover from certain transients if normal pressurizer spray is not available.
1.2 Proposed Technical Specification Changes TS 3.4.11, Pressurizer Power Operated Relief Valves (PORVs) requires closing the block valves and removing power if a PORV is inoperable and/or incapable of being manually cycled.
Closing the block valve will prevent excessive leakage through the PORV. Closing and deenergizing block valves is intended to mitigate PORV related issues. It does not ensure the operability of the PORVs. The current TS 3.4.11 requirement to place a PORV in manual control when its associated block valve is inoperable does not preserve pressurizer pressure control if the affected PORV is unable to stroke. Pressure control via the associated PORV is not possible when the block valve cannot be opened. The purpose of the proposed changes is to remove the requirements to perform TS Required Actions for block valve inoperability if the block valve is inoperable only because it was closed and deenergized as required by TS actions due to its associated PORV being inoperable. The actions required for inoperable block valves are to place the associated PORV in manual control and/or restore the block valve to Operable status. These are the actions that will not be required by the proposed change if the block valve is inoperable because of Required Actions taken due to PORV inoperability.
The changes to the TS are implemented by adding notes to the appropriate Conditions for block valve operability in TS 3.4.11. In accordance with the NRC staff approved-TSTF-309, the licensee proposed changes that would revise TS 3.4.11. Specifically, the licensee proposed the following changes to adopt TSTF-309:
For Braidwood and Byron:
For Required Actions C.1 and C.2 the following note is added. Required Action C.1 is to place the PORV in manual control and required action C.2 is to restore the block valve to Operable status. These actions will not need to be performed if the block valve is inoperable due to Required Action B.2.
The following text will be added to Braidwood and Byron TS 3.4.11, Condition C (addition in bold):
CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve inoperable.
NOTE-----------
Required Actions C.1 and C.2 do not apply when block valve is inoperable solely as a result of complying with Required Action B.2.
C.1 Place associated PORV in manual control.
AND C.2 Restore block valve to OPERABLE status.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 72 hours OR In accordance with the Risk Informed Completion Time Program For Required Action F.1 the following note is added. Required Action F.1 is to restore the block valve to Operable status. Required Action F.1 is not required to be performed if the block valve is inoperable due to Required Action B.2.
The following text will be added to Braidwood and Byron TS 3.4.11, Condition F (addition in bold):
CONDITION REQUIRED ACTION COMPLETION TIME F. Two block valves inoperable.
NOTE-----------
Required Actions F.1 does not apply when block valve is inoperable solely as a result of complying with Required Action B.2.
F.1 Restore one block valve to OPERABLE status.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> For Ginna:
For Required Actions C.1 and C.2 the following note is added. Required Action C.1 is to place the associated PORV in manual control. Required Action C.2 is to restore the block valve to Operable status, Verify the opposite trainer PORV and block valve are Operable, and restore the block valve to Operable status. These actions do not need to be performed if the block valve is inoperable due to Required Actions B.2 or F.3.
The following text will be added to Ginna TS 3.4.11, Condition C (addition in bold):
CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve inoperable.
NOTE------------------
Required Actions C.1 and C.2 do not apply when block valve is inoperable solely as a result of complying with Required Action B.2 or F.3.
C.1 Place associated PORV in manual control.
AND C.2.1 Restore block valve to OPERABLE status.
OR 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 days C.2.2.2 Verify Opposite Train PORV and PORV Block Valve are OPERABLE.
AND C.2.2.3 Restore PORV Block Valve to OPERABLE status.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 days OR
NOTE-------
Not applicable if there is a loss of function.
In accordance with the Risk Informed Completion Time Program For Required Actions D.1 and D.2 the following note is added. Required Action D.1 is to place the associated PORVs in manual control. Required Action D.2 is to restore at least one block valve to Operable status. These actions do not need to be performed if the block valve is inoperable due to Required Actions B.2 or F.3.
The following text will be added to Ginna TS 3.4.11, Condition D (addition in bold):
CONDITION REQUIRED ACTION COMPLETION TIME D. One block valve inoperable.
NOTE----------------
Required Actions D.1 and D.2 do not apply when block valve is inoperable solely as a result of complying with Required Action B.2 or F.3.
D.1 Place associated PORV in manual control.
AND D.2 Restore at least on block valve to OPERABLE status.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 72 hours 1.3 Variations from TSTF-309, Revision 2 The NRC staff notes the following variations from the TS changes described in TSTF-309, Revision 2. These variations are summarized below.
The proposed changes to TS 3.4.11 for Braidwood, Byron, and Ginna are different from the traveler because of differences in numbering of plant TS compared to the numbering of STS TSTF-309, Revision 2, is based on NUREG-1431, Revision 1 on which TSTF-309 is based. NUREG-1431, Revision 1, has two Conditions that address PORVs that are inoperable and cannot be manually cycled. These are Condition B, for one or two PORVs inoperable, and Conditions E for two or three PORVs inoperable. Both Conditions B and E require that the associated block valves be closed and deenergized.
In the traveler, the Conditions applicable to block valve Operability are Conditions C and F. Therefore, TSTF-309, Revision 2, the notes are specifically added to the Required Actions for Conditions C and F.
o Braidwood and Byron also have two Conditions that address PORVs that are inoperable and not able to be stroked. Condition B is for a single PORV that is inoperable and not capable of being stroked. Condition B requires the block valve be closed and have power removed. Condition E is for two PORVs that are inoperable and not capable of being stroked. Condition E requires the plant be shutdown and does not require any actions be taken for the block valves. Since Condition E does not direct any action for the block valves, only Condition B needs to be addressed in the added notes for Braidwood and Byron. At Braidwood and Byron, the Conditions that apply to inoperable block valves are Conditions C and F which are the same as the traveler. The notes are proposed to be added to the Required Actions for Conditions C and F in the Braidwood and Byron TS.
o Ginna has two conditions that address PORVS that are inoperable. Condition B is for a single PORV that is inoperable. Condition F is for two PORVs inoperable.
Both of these Conditions require the associated block valve(s) be closed and deenergized. Therefore, both Condition B and F are addressed in the added notes. For Ginna, the Conditions that apply to inoperable block valves are Conditions C and D. Therefore, the notes are proposed to be added to the Required Actions for Conditions C and D in the Ginna TS.
1.4 Proposed Changes to Technical Specification Bases Consistent with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(a)(1), the licensee submitted corresponding changes to the TS Bases, for information only, that provide the reasons for the proposed TSs changes. The regulation at 10 CFR 50.36(a)(1) states that a summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the TS. The licensee shall make changes to the plant TS Bases in accordance with the TS Bases Control Program, found at TS 5.5.14 for Byron and Braidwood, and at TS 5.5.13 for Ginna.
2.0 REGULATORY EVALUATION
2.1 Regulatory Requirements Per 10 CFR Part 50.90, whenever a holder of a license wishes to amend the license, including technical specifications in the license, an application for amendment must be filed, fully describing the changes desired. Under 10 CFR Part 50.92(a), determinations on whether to grant an applied-for license amendment are to be guided by the considerations that govern the issuance of initial licenses or construction permits to the extent applicable and appropriate. Both the common standards for licenses and construction permits in 10 CFR Part 50.40(a), and those specifically for issuance of operating licenses in 10 CFR Part 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public.
The regulation in 10 CFR 50.36, Technical specifications, provides the regulatory requirements for the content of the TS. It requires, in part, that a summary statement of the bases for such specifications shall be included by applicants for a license authorizing operation of a production or utilization facility. Specifically, 10 CFR 50.36(c) requires that TS include items in five specific categories related to station operation. These categories are (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) Surveillance requirements; (4) design features; and (5) administrative controls.
The regulation at 10 CFR 50.36(b) requires that:
Each license authorizing operation of a utilization facility will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to [10 CFR] 50.34 [Contents of applications; technical information]. The Commission may include such additional technical specifications as the Commission finds appropriate.
In accordance with 10 CFR 50.36(c)(2), LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When LCOs are not met, the licensee must shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met. In addition, 10 CFR 50.36(c)(2)(ii)(C) requires a TS LCO of a nuclear reactor must be established for a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
2.2 Guidance TSTF-309, Revision 2, was incorporated by the NRC into Revision 2 of NUREG-1431 (ML011840211) and has been maintained through the current revision. Additional, though the proposed changes to the STS via TSTF-309 were developed based on changes to Revision 2 of NUREG-1431, the NRC staff review of the LAR includes consideration of whether the proposed changes are consistent with the latest revisions. NUREG-1431, Revision 5.0, Standard Technical Specifications, Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases, dated September 2021 (ML21259A155 and ML21259A159, respectively) provide example TS to meet the requirements in 10 CFR 50.36(c) for a standard plant design.
The NRC staffs guidance for the review of TSs is provided in chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP),
March 2010 (ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared STSs for each of the LWR nuclear designs. Accordingly, the NRC staffs license amendment request review includes consideration of whether the proposed changes are consistent with the STSs, as modified by NRC approved travelers.
3.0 TECHNICAL EVALUATION
The proposed amendments are based on the NRC-approved TSTF-309, Revision 2. The NRC staffs evaluation (SE) of the proposed amendments relies upon the NRC staffs previous approval of TSTF-309, Revision 2. The regulatory framework that the NRC staff used to determine the acceptability of the proposed changes consists of the requirements listed in Section 2.3 of this SE. The NRC staff reviewed the proposed TS changes to determine whether they meet the standards in 10 CFR 50.36(c)(2).
3.1 Proposed Changes to TS 3.4.11 Proposed Changes to Braidwood and Byron Required Actions C and F In accordance with NRC-approved TSTF-309, Revision 2, the licensee proposed to add a note to each of Required Actions C and F. The notes allow that the Required Actions to place the PORV in manual control and restore the block valve to Operable not be performed if the block valve(s) is inoperable solely as a result of Required Action B.2 imposed due to PORV inoperability. The NRC staff finds the proposed change is acceptable because the actions taken for the PORV inoperability per Condition B are adequate to address the inoperability of the relief path(s), including the block valve(s).
Conditions C and F are intended to be applied for block valve inoperability related to block valve equipment issues, not Required Actions due to PORV issues. Therefore, declaring the block valves inoperable due to actions required for PORV inoperability are not needed.
Proposed Changes to Ginna Actions C and D In accordance with NRC-approved TSTF-309, Revision 2, the licensee proposed to add a note to each of Required Actions C and D. The notes allow that the Required Actions to place the PORV in manual control and restore the block valve to Operable not be performed if the block valve(s) is inoperable solely as a result of Required Action B.2 or F.3 imposed due to PORV inoperability. The NRC staff finds the proposed change is acceptable because the actions taken for the PORV inoperability per Conditions B and F are adequate to address the inoperability of the relief path(s), including the block valve(s). Conditions C and D are intended to be applied for block valve inoperability related to block valve equipment issues, not Required Actions due to PORV issues.
Therefore, declaring the block valves inoperable due to actions required for PORV inoperability are not needed.
The NRC staff determined the proposed changes in TS 3.4.11 for Braidwood, Byron, and Ginna are acceptable because the added notes allow the operators to not take actions that are not needed to assure the safety of the plants. Additionally, other Required Actions in TS 3.4.11 ensure that the requirements for the PORV relief paths including the PORVs and block valves are adequate. The changes are consistent with the NUREG-1431, Revision 5, and the NRC-approved TSTF-309, Revision 2. Therefore, the NRC staff concludes that the corresponding proposed changes to the CEG facilities TS in section 1.2 of this SE continue to meet the requirements of 10 CFR 50.36(c)(2).
3.2 Variations As discussed in Section 1.3 of this SE, the NRC staff noted variations from TSTF-309, Revision 2, related to the use of different numbering used in the Braidwood, Byron, and Ginna TSs. The NRC staff reviewed these variations and finds that they are acceptable because they are administrative in nature and do not affect the applicability of TSTF-309, Revision 2, to the Braidwood, Byron, and Ginna TSs.
3.3 TS Change Consistency The NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with chapter 16.0 of the SRP and are therefore acceptable.
4.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NO. 243 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-72 AMENDMENT NO. 243 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-77 AMENDMENT NO. 241 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-37 AMENDMENT NO. 241 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-66 AMENDMENT NO. 159 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-18 CONSTELLATION ENERGY GENERATION, LLC BRAIDWOOD STATION, UNITS 1 AND 2 BYRON STATION, UNIT NOS. 1 AND 2 R.E. GINNA NUCLEAR POWER PLANT DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, STN 50-455, AND 50-244 Application (i.e., initial and supplements)
Safety Evaluation Date February 27, 2025, ML25058A246 September 2, 2025 1.0 INTRODUCTION Constellation Energy Generation, LLC (CEG, the licensee) requested changes to the technical specifications (TSs) for Braidwood Station, Units 1 and 2 (Braidwood), Byron Station, Unit Nos. 1 and 2 (Byron), and R.E. Ginna Nuclear Power Plant (Ginna) by license amendment request (LAR, application) to the U.S. Nuclear Regulatory Commission (NRC, the Commission).
The proposed changes would revise the TS based on Technical Specifications Task Force (TSTF) Traveler 309, Revision 2, Revise Pressurizer PORV [Power Operated Relief Valve]
Actions to not require cycling of block valve when closed for isolation, (TSTF-309) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML040620179)).
Specifically, TSTF-309 revises the standard TS (STS) by modifying TS 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), to add notes stating that the Required Actions do not apply if the PORV block valve was declared inoperable solely as a result of complying with other Required Actions in TS 3.4.11.
2.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Illinois and New York State officials were notified of the proposed issuance of the amendments on August 5, 2025. The relevant officials had no comments.
3.0 ENVIRONMENTAL CONSIDERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in Title 10 of the Code of Federal Regulations (10 CFR), part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, which was published in the Federal Register on April 15, 2025 (90 FR 15727), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; AND R.E. GINNA NUCLEAR POWER PLANT - ISSUANCE OF AMENDMENTS TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-309 (EPID L-2025-LLA-0043) DATED SEPTEMBER 2, 2025 DISTRIBUTION:
PUBLIC RidsNrrDorlLpl1 Resource RidsNrrDorlLpl3 Resource RidsRgn1MailCenter Resource RidsRgn3MailCenter Resource RidsNrrLASLent Resource RidsNrrLAKEntz Resource RidsAcrs_MailCTR Resource RidsNrrPMConstellation Resource RidsNrrPMBraidwood Resource RidsNrrPMByron Resource RidsNrrPMREGinna Resource RidsNrrDssStsb Resource RidsNrrDssScpb Resource BRothberg, NRR RHernandez, NRR SSmith, NRR Accession No.: ML25233A262
- SE provided via memorandum OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC*
NAME SWall SLent SMehta DATE 08/21/2025 08/26/2025 07/31/2025 OFFICE NRR/DSS/SCPB/BC*
NRR/DORL/LPL3/BC(A)
NRR/DORL/LPL3/PM NAME MValentin IBerrios SWall DATE 07/31/2025 09/02/2025 09/02/2025 OFFICIAL RECORD COPY